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Title: Concentration of uranium and plutonium in unsaturated spent fuel tests.

Abstract

Commercial spent fuel is being tested under oxidizing conditions at 90 C in drip tests with simulated groundwater to evaluate its long-term performance in a potential repository at Yucca Mountain [1-4]. The tests allow us to monitor the dissolution behavior of the spent fuel matrix and the release rates of individual radionuclides. This paper reports the U and Pu concentrations in the leachates of drip tests during 3.7 years of reaction. Changes in these concentrations are correlated with changes in the measured pH and the appearance of alteration products on the fuel surface. Although there is little thermodynamic information at 90 C for either uranyl or plutonium compounds, some data are available at 25 C [5-8]. The literature data for the U and Pu solubilities of U and Pu compounds were compared to the U and Pu concentrations in the leachates. We also compare Wilson's [9] U and Pu concentrations in semi-static tests at 85 C on spent fuel with our results.

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
10740
Report Number(s):
ANL/CMT/CP-96157
TRN: US0103826
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: 3rd Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998; Other Information: PBD: 15 Apr 1998
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; PLUTONIUM; PLUTONIUM COMPOUNDS; SPENT FUELS; THERMODYNAMICS; URANIUM; YUCCA MOUNTAIN; GROUND WATER; CORROSION RESISTANCE; RADIOACTIVE WASTE DISPOSAL; WASTE FORMS; DISSOLUTION; LEACHATES; CONCENTRATION RATIO; RADIONUCLIDE MIGRATION; SOLUBILITY

Citation Formats

Finn, P A. Concentration of uranium and plutonium in unsaturated spent fuel tests.. United States: N. p., 1998. Web.
Finn, P A. Concentration of uranium and plutonium in unsaturated spent fuel tests.. United States.
Finn, P A. 1998. "Concentration of uranium and plutonium in unsaturated spent fuel tests.". United States. https://www.osti.gov/servlets/purl/10740.
@article{osti_10740,
title = {Concentration of uranium and plutonium in unsaturated spent fuel tests.},
author = {Finn, P A},
abstractNote = {Commercial spent fuel is being tested under oxidizing conditions at 90 C in drip tests with simulated groundwater to evaluate its long-term performance in a potential repository at Yucca Mountain [1-4]. The tests allow us to monitor the dissolution behavior of the spent fuel matrix and the release rates of individual radionuclides. This paper reports the U and Pu concentrations in the leachates of drip tests during 3.7 years of reaction. Changes in these concentrations are correlated with changes in the measured pH and the appearance of alteration products on the fuel surface. Although there is little thermodynamic information at 90 C for either uranyl or plutonium compounds, some data are available at 25 C [5-8]. The literature data for the U and Pu solubilities of U and Pu compounds were compared to the U and Pu concentrations in the leachates. We also compare Wilson's [9] U and Pu concentrations in semi-static tests at 85 C on spent fuel with our results.},
doi = {},
url = {https://www.osti.gov/biblio/10740}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 15 00:00:00 EDT 1998},
month = {Wed Apr 15 00:00:00 EDT 1998}
}

Conference:
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